• 제목/요약/키워드: integrity assessment

검색결과 554건 처리시간 0.024초

사각 감육을 고려한 중수로 공급자관 파열압력 평가 (Evaluation of the Burst Pressure for Rectangular Wall-thinning of CANDU Feeder Pipe)

  • 김광수;김민규;조두호;정재준
    • 한국압력기기공학회 논문집
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    • 제17권1호
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    • pp.28-35
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    • 2021
  • The flow accelerated corrosion (FAC) is one of significant aging and degradation mechanism and can affect structural integrity of CANDU feeder pipes. Pipe burst can occur under normal operation pressure (min. 10 MPa) if wall-thinning of the feeder pipe due to FAC is accumulated. Previous studies considered simple shapes of feeder pipe with local wall-thinning in order to conservatively assess structural integrity of wall-thinned feeder pipe. In this paper, a new FE model is developed, having an actual shape of the feeder pipe (double bent) as well as the actual wall-thinning shape and location based on the in-service inspection result. Then, the burst pressure assessment of the wall-thinned feeder pipe is performed using lower bound limit load analysis considering elastic-perfectly plastic material. In addition, an improved formulation to predict the burst pressure of the wall-thinned feeder pipe is presented and the safety margin is compared with an existing assessment method.

Condition assessment of aged underground water tanks-Case study

  • Zafer Sakka;Ali Saleh;Thamer Al-Yaqoub;Hasan Karam;Shaikha AlSanad;Jamal Al-Qazweeni;Mohammad Mosawi;Husain Al-Baghli
    • Structural Engineering and Mechanics
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    • 제90권5호
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    • pp.493-504
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    • 2024
  • This paper presents the methodology and results for the investigation of the structural safety of 40 aged underground water tanks to support the weight of photovoltaic (PV) systems that were supposed to be placed on their roof reinforced concrete (RC) slabs. The investigation procedure included (1) review of available documents; (2) visual inspection of the roof RC slabs; (3) carrying out a series of nondestructive (ND) tests; and (4) analysis of results. Out of the 40 tanks, eleven failed the visual inspection phase and were discarded from further investigation. The roof RC slabs of the tanks that passed the visual inspection were subjected to a series of ND tests that included infrared thermography, impact echo, ultrasonic pulse velocity (UPV), Schmidt hammer, concrete core compressive strength, and water-soluble chloride content. The NDT results proved that eight more tanks were not suitable to support the PV systems. Based on the results of the visual inspection and testing, a probabilistic decision-making criterion was established to reach a decision regarding the structural integrity of the roof slabs. The study concluded that the condition of the drainage filter was essential in protecting the tanks and its intact presence can be used as a strong indication of the structural integrity of the roof RC slabs.

가압열충격 사고시 클래드 하부균열 안전성 평가 방법에 관한 연구 (A Study on the Integrity Evaluation Method of Subclad Crack Under Pressurized Thermal Shock)

  • 김영진;김진수;구본걸;최재붕;박윤원
    • 대한기계학회논문집A
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    • 제25권7호
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    • pp.1139-1146
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    • 2001
  • The reactor pressure vessel(RPV) is usually cladded with stainless steel to prevent corrosion and radiation embrittlement, and a number of subclad cracks have been found during an in-service-inspection. These subclad cracks should be assured for a safe operation under normal conditions and faulted conditions such as pressurized thermal shock(PTS). Currently available integrity assessment procedure for an RPV, ASME Code Sec. XI, are built on the basis of linear fracture mechanics (LEFM). In PTS condition, however, thermal stress and mechanical stress give rise to high tensile stress at the cladding and elastic-plastic behavior is expected in this area. Therfore, ASME Code Sec. XI is overly conservative in assessing the structural integrity under PTS condition. In this paper, the fracture parameter (stress intensity factor, K, and RT(sub)NDT) from elastic analysis using ASME Sec. XI and finite element method were validated against 3-D elastic-plastic finite element analyses. The difference between elastic and elastic-plastic analysis became significant with increasing crack depth. Therfore, it is recommended to perform elastic-plastic analysis for the accurate assessment of subclad cracks under TPS which causes plastic deformation at the cladding.

이중연료엔진의 연료가스공급시스템에 대한 안전무결도 기반 안전계장시스템 설계 (SIS Design for Fuel Gas Supply System of Dual Fuel Engine based on Safety Integrity Level(SIL))

  • 강낙원;박재홍;정정호;나성
    • 대한조선학회논문집
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    • 제49권6호
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    • pp.447-460
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    • 2012
  • In this study, the shutdown system of the fuel gas supply system is designed based on the Safety Integrity Level of IEC 61508 and IEC 61511. First of all, the individual risk($10^{-4}$/year) and the risk matrix which are the risk acceptance criteria are set up for the qualitative risk assessment such as the HAZOP study. The natural gas leakage at the gas supply pipe is identified as the highest risk among the hazards identified through the HAZOP study and as a safety instrumented function the shutdown function for leakage was defined. SIL 2 and PFD($2.5{\cdot}10^{-3}$) for the shutdown function are determined by the layer of protection analysis(LOPA). The shutdown system(SIS) carrying out the shutdown function(SIF) is verified and designed according to qualitative and quantitative requirements of IEC 61508 and IEC 61511. As a result of SIL verification and SIS conceptual design, the shutdown system is composed of two gas detectors voted 1oo2, one programmable logic solver, and two shutdown valve voted 1oo2.

Potential Probiotic Characteristics and Safety Assessment of Lactobacillus rhamnosus SKG34 Isolated from Sumbawa Mare's Milk

  • Sujaya, I Nengah;Suwardana, Gede Ngurah Rsi;Gotoh, Kazuyoshi;Sumardika, I Wayan;Nocianitri, Komang Ayu;Sriwidyani, Ni Putu;Putra, I Wayan Gede Artawan Eka;Sakaguchi, Masakiyo;Fatmawati, Ni Nengah Dwi
    • 한국미생물·생명공학회지
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    • 제50권1호
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    • pp.51-62
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    • 2022
  • Lactobacillus rhamnosus SKG34 (LrSKG34), a potential probiotic strain, was successfully isolated from Sumbawa Mare's milk. Our previous studies showed that the strain is resistant to gastrointestinal conditions, possesses antioxidant activity, and lowers blood cholesterol levels. Further clarification of the potential probiotic characteristics and safety assessment are necessary. This study aimed to evaluate the adhesion of LrSKG34 to Caco-2 cell monolayers and its effect on mucosal integrity in vitro. We also examined the LrSKG34 safety profile based on antimicrobial susceptibility testing, haemolytic activity determination, Caco-2 cell monolayer translocation evaluation, and in vivo investigation of the effect of LrSKG34 on the physiology, biochemical markers, and histopathological appearance of major organs in an animal model. LrSKG34 attached to Caco-2 cell monolayers and maintained mucosal integrity in vitro. The typical resistance of lactobacilli to ciprofloxacin, gentamicin, vancomycin, trimethoprim-sulfamethoxazole, and metronidazole was confirmed for LrSKG34. No haemolytic activity was observed on blood agar plates, and no LrSKG34 translocation was observed in Caco-2 cell monolayers. Administration of LrSKG34 to Sprague-Dawley rats did not adversely affect body weight. No abnormalities in hematological parameters, serum biochemistry levels, or histopathological structures of major organs were observed in LrSKG34-treated rats. Collectively, the results implicate LrSKG34 as a promising and potentially safe probiotic candidate for further development.

원전 배관의 결함 평가를 위한 해석 (Analysis for Defect Evaluation of Pipes in Nuclear Power Plant)

  • 이준성
    • 한국산학기술학회논문지
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    • 제14권7호
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    • pp.3121-3126
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    • 2013
  • 원전 배관의 건전성평가는 원자로 안전을 위해 중요하며 결함발견 시 반드시 건전성을 확보해야만 한다. 균열을 갖는 구조물에 대한 정확한 응력확대계수 해석과 균열성장속도는 파괴강도와 피로수명을 평가하는데 필요로 한다. 피로설계와 수명평가는 배관, 산업공장장비 등과 같은 구조물을 설계하는데 극히 중요하다. 응력확대계수를 이용한 균열간의 상호 간섭해석은 유한요소법으로 구하였다. 내압을 받는 원통형구조물의 경우 표면균열의 인접점에서 간섭이 가장 크게 일어남을 확인하였다. 또한, 반복하중 균열에 대해서는 균열 성장평가와 더불어 피로하중에 의한 균열진전을 예측하기 위한 피로해석을 수행하였다.

High Temperature Structural Integrity Evaluation Method and Application Studies by ASME-NH for the Next Generation Reactor Design

  • Koo, Gyeong-Hoi;Lee, Jae-Han
    • Journal of Mechanical Science and Technology
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    • 제20권12호
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    • pp.2061-2078
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    • 2006
  • The main purpose of this paper is to establish the high temperature structural integrity evaluating procedures for the next generation reactors, which are to be operated at over 500$^{\circ}C$ and for 60 years. To do this, comparison studies of the high temperature structural design codes and assessment procedures such as the ASME-NH (USA), RCC-MR (France), DDS (Japan), and R5 (UK) are carried out in view of the accumulated inelastic strain and the creep-fatigue damage evaluations. Also the application procedures of the ASME-NH rules with the actual thermal and structural analysis results are described in detail. To overcome the complexity and the engineering costs arising from a real application of the ASME-NH rules by hand, all the procedures established in this study such as the time-dependent primary stress limits, total accumulated creep ratcheting strain limits, and the creep-fatigue damage limits are computerized and implemented into the SIE ASME-NH program. Using this program, the selected high temperature structures subjected to two cycle types are evaluated and the parametric studies for the effects of the time step size, primary load, number of cycles, normal temperature for the creep damage evaluations and the effects of the load history on the creep ratcheting strain calculations are investigated.

CANDU형 원전 경년열화 감시시스템(Aging Monitor) 개발 (Development of CANDU Reactor Aging Monitor)

  • 김홍기;최영환;고한옥
    • 한국압력기기공학회 논문집
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    • 제5권2호
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    • pp.13-19
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    • 2009
  • As the operating time in nuclear power plants (NPPs) increases, the integrity of nuclear components may be continually degraded due to aging effects of systems, structures and components. Recently, a number of NPPs are being operated beyond their design life to produce more electricity without shutting down. The critical issue in extending a lifetime is to maintain the level of safety during the extended operation period while satisfying the international regulatory standards. Therefore, it is beneficial to build a monitoring system to measure an aging status. In this paper, the Aging Monitor (AM) based on lots of aging database obtained from the operating plants and research results on the aging effects was developed to monitor, manage and evaluate the aging phenomena systematically and effectively in NPPs. The AM for the CANDU is divided into 6 modules: (1) Aging Alarm/Coloring Monitor, (2) Aging Database, (3) Aging Document, (4) Real-time Integrity Monitor, (5) Surveillance and Inspection Management System, and (6) Continued Operation and Periodic Safety Review (PSR) Safety Evaluation. The proposed system is expected to provide the integrity assessment for the major mechanical components of an NPP under concurrent working environments.

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AES를 이용한 스트림 암호 개발 (Development of Stream Cipher using the AES)

  • 김성기;김길호;조경연
    • 한국통신학회논문지
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    • 제38C권11호
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    • pp.972-981
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    • 2013
  • 미래전의 양상은 네트워크중심전(NCW: Network Centric Warfare)으로 바뀌고 있으며, 다양한 전력 요소가 유무선 네트워크와 상호 유기적인 연결을 통한 첨단 정보통신기술의 활용이 네트워크중심전의 구현에 핵심 요소라고 할 수 있다. 그리고 네트워크중심전에 사용되는 다양한 정보들은 기밀성과 무결성이 우수하면서 신뢰성 있는 실시간 처리만이 빠른 상황판단을 할 수 있고, 이는 전쟁 승리의 핵심이 된다. 본 논문에서는 네트워크중심전 구현에 핵심 기술 중 하나인 암호 알고리즘으로서 128비트 출력 스트림 암호를 개발했다. 개발한 스트림 암호는 AES를 기반으로 변형된 OFB모드를 적용하여 기밀성과 무결성 그리고 하드웨어로 구현하여 실시간처리와 안전성이 우수하다.

Power Distribution Network Modeling using Block-based Approach

  • Chew, Li Wern
    • 마이크로전자및패키징학회지
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    • 제20권4호
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    • pp.75-79
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    • 2013
  • A power distribution network (PDN) is a network that provides connection between the voltage source supply and the power/ground terminals of a microprocessor chip. It consists of a voltage regulator module, a printed circuit board, a package substrate, a microprocessor chip as well as decoupling capacitors. For power integrity analysis, the board and package layouts have to be transformed into an electrical network of resistor, inductor and capacitor components which may be expressed using the S-parameters models. This modeling process generally takes from several hours up to a few days for a complete board or package layout. When the board and package layouts change, they need to be re-extracted and the S-parameters models also need to be re-generated for power integrity assessment. This not only consumes a lot of resources such as time and manpower, the task of PDN modeling is also tedious and mundane. In this paper, a block-based PDN modeling is proposed. Here, the board or package layout is partitioned into sub-blocks and each of them is modeled independently. In the event of a change in power rails routing, only the affected sub-blocks will be reextracted and re-modeled. Simulation results show that the proposed block-based PDN modeling not only can save at least 75% of processing time but it can, at the same time, keep the modeling accuracy on par with the traditional PDN modeling methodology.